OA00647A - Method and device for flattening the axial neutron flux of a nuclear reactor. - Google Patents
Method and device for flattening the axial neutron flux of a nuclear reactor.Info
- Publication number
- OA00647A OA00647A OA50753A OA50753A OA00647A OA 00647 A OA00647 A OA 00647A OA 50753 A OA50753 A OA 50753A OA 50753 A OA50753 A OA 50753A OA 00647 A OA00647 A OA 00647A
- Authority
- OA
- OAPI
- Prior art keywords
- flattening
- nuclear reactor
- neutron flux
- axial neutron
- axial
- Prior art date
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/005—Flux flattening
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/16—Details of the construction within the casing
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/36—Assemblies of plate-shaped fuel elements or coaxial tubes
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Production Of Liquid Hydrocarbon Mixture For Refining Petroleum (AREA)
- Feeding And Controlling Fuel (AREA)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
BE496961 | 1962-08-31 |
Publications (1)
Publication Number | Publication Date |
---|---|
OA00647A true OA00647A (en) | 1966-07-15 |
Family
ID=3844703
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
OA50753A OA00647A (en) | 1962-08-31 | 1964-12-05 | Method and device for flattening the axial neutron flux of a nuclear reactor. |
Country Status (7)
Country | Link |
---|---|
BE (1) | BE621955A (en) |
DE (1) | DE1464571A1 (en) |
FR (1) | FR1361744A (en) |
GB (1) | GB980943A (en) |
LU (1) | LU44075A1 (en) |
NL (1) | NL295527A (en) |
OA (1) | OA00647A (en) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2850069C2 (en) * | 1978-11-18 | 1983-01-05 | Kernforschungsanlage Jülich GmbH, 5170 Jülich | Target for spallation neutron sources |
-
0
- NL NL295527D patent/NL295527A/xx unknown
- BE BE621955D patent/BE621955A/xx unknown
-
1963
- 1963-07-04 FR FR940313A patent/FR1361744A/en not_active Expired
- 1963-07-17 LU LU44075D patent/LU44075A1/xx unknown
- 1963-08-20 GB GB32969/63A patent/GB980943A/en not_active Expired
- 1963-08-27 DE DE19631464571 patent/DE1464571A1/en active Pending
-
1964
- 1964-12-05 OA OA50753A patent/OA00647A/en unknown
Also Published As
Publication number | Publication date |
---|---|
NL295527A (en) | |
BE621955A (en) | |
GB980943A (en) | 1965-01-20 |
DE1464571A1 (en) | 1969-04-10 |
FR1361744A (en) | 1964-05-22 |
LU44075A1 (en) | 1963-09-17 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CH449128A (en) | Method for recharging a nuclear reactor and device for implementing the method | |
CH413139A (en) | Stopping device of a nuclear reactor | |
CH398816A (en) | Process for pressurizing a nuclear reactor and pressurizer for implementing the process | |
FR1323555A (en) | Method for detecting the disturbance of a body and device for its implementation | |
FR1456196A (en) | Method and device for charging nuclear reactors | |
OA00647A (en) | Method and device for flattening the axial neutron flux of a nuclear reactor. | |
FR1357863A (en) | Shutdown device for nuclear reactors | |
CH458555A (en) | Safety device for causing the neutron shutdown of a nuclear reactor | |
CH512131A (en) | Method and device for controlling a neutron flux | |
FR1356683A (en) | Process for the operation of a nuclear reactor and nuclear reactor for its implementation | |
FR1329117A (en) | Method and apparatus for controlling a nuclear reactor | |
FR1355718A (en) | Method and devices for controlling the criticality of a nuclear reactor | |
FR1347127A (en) | Lifting device for control rods of a nuclear reactor | |
CH416857A (en) | Handling device for reloading a nuclear reactor with fuel | |
FR1222219A (en) | Method and device for the detection of a neutron flux | |
GB997925A (en) | Device for determining the rate of increase of the neutron flux in a nuclear reactor | |
FR1457499A (en) | Method and device for controlling a nuclear reactor | |
FR1323699A (en) | Experimentation loop for nuclear reactors | |
BE612006A (en) | Method and device for the precise control of the power of a nuclear suspension reactor in the event of a constant demand for power | |
BE603275A (en) | Experimental irradiation loop for nuclear reactor | |
FR1270554A (en) | Solid moderator stacking method and device for nuclear reactors | |
FR1375685A (en) | Device for the axial permutation of the fuel elements of a nuclear reactor | |
FR1328539A (en) | Fuel element centering device for nuclear reactor | |
FR2042513A1 (en) | DEVICE FOR STABILIZING THE CORE OF A NUCLEAR REACTOR | |
FR1298516A (en) | Method and device for controlling a nuclear reactor |